S. Yoshimura, T. Miyamura, Tomonori Yamada, H. Akiba, H. Kiyoura
This research presents the recent development of the analysis system ADVENTURE, i.e., a parallel structural analysis solver ADVENTURE_Solid Ver.2 and its pre- / post-modules, towards petascale computers such as the K computer with 10 petaflops peak performance, as well as its application to three-dimensional finite element seismic response analyses of a full-scale integrated model of the boiling water reactor and reactor building of Unit 1 at the Fukushima-Daiichi Nuclear Power Plant sub-jected to the 2011 off the Pacific coast of Tohoku Earthquake of 9.0 Mw occurring on March 11, 2011. Here, we precisely modeled its pressure vessel, containment vessel, suppression chamber, vent piping, a number of supports and the reactor building with a 200 million DOF finite element mesh. Then, we successfully solved its dynamic response in 65 s. We report our research results in two papers, i.e., Part I and Part II. Part I （ this paper ） reports the developed analysis method, model construction, verification of the analysis model, and computation performance. Part II reports the results of an eigen-analysis and a seismic response analysis. Finally, we concluded some key roles of petascale simulation for such practical and socially important problems.
{"title":"Seismic Response Analysis of Unit 1 of Fukushima-Daiichi Nuclear Power Plant During the 2011 Off the Pacific Coast of Tohoku Earthquake Using Three-Dimensional Finite Element Method (1st Report: Development of Analysis Method, Model Construction and Verification of Analysis Performance)","authors":"S. Yoshimura, T. Miyamura, Tomonori Yamada, H. Akiba, H. Kiyoura","doi":"10.3327/TAESJ.J18.001","DOIUrl":"https://doi.org/10.3327/TAESJ.J18.001","url":null,"abstract":"This research presents the recent development of the analysis system ADVENTURE, i.e., a parallel structural analysis solver ADVENTURE_Solid Ver.2 and its pre- / post-modules, towards petascale computers such as the K computer with 10 petaflops peak performance, as well as its application to three-dimensional finite element seismic response analyses of a full-scale integrated model of the boiling water reactor and reactor building of Unit 1 at the Fukushima-Daiichi Nuclear Power Plant sub-jected to the 2011 off the Pacific coast of Tohoku Earthquake of 9.0 Mw occurring on March 11, 2011. Here, we precisely modeled its pressure vessel, containment vessel, suppression chamber, vent piping, a number of supports and the reactor building with a 200 million DOF finite element mesh. Then, we successfully solved its dynamic response in 65 s. We report our research results in two papers, i.e., Part I and Part II. Part I （ this paper ） reports the developed analysis method, model construction, verification of the analysis model, and computation performance. Part II reports the results of an eigen-analysis and a seismic response analysis. Finally, we concluded some key roles of petascale simulation for such practical and socially important problems.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.3327/TAESJ.J18.001","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437270","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Atsufumi YOSHIZAWA, Kyoko OBA and Masaharu KITAMURA Research Center for Safe and Secure Society, Nagaoka University of Technology, 1603–1 Kamitomiokamachi, Nagaoka-shi, Niigata 940–2188, Japan Japan Atomic Energy Agency, 2–2–2 Uchisaiwai-cho, Chiyoda-ku, Tokyo 100–8577, Japan Research Institute for Technology Management Strategy (TeMS) Co., Ltd., 6–6–40–403 Aobaaramaki-aza, Aoba-ku, Sendai-shi, Miyagi 890–8579, Japan (Received December 28, 2018; accepted in revised form January 25, 2019; published online April 26, 2019)
{"title":"Enhancing Emergency Response in the Field Based on Analysis of Workload Distribution at Fukushima Daiichi Nuclear Power Station","authors":"Atsufumi Yoshizawa, K. Oba, M. Kitamura","doi":"10.3327/TAESJ.J18.041","DOIUrl":"https://doi.org/10.3327/TAESJ.J18.041","url":null,"abstract":"Atsufumi YOSHIZAWA, Kyoko OBA and Masaharu KITAMURA Research Center for Safe and Secure Society, Nagaoka University of Technology, 1603–1 Kamitomiokamachi, Nagaoka-shi, Niigata 940–2188, Japan Japan Atomic Energy Agency, 2–2–2 Uchisaiwai-cho, Chiyoda-ku, Tokyo 100–8577, Japan Research Institute for Technology Management Strategy (TeMS) Co., Ltd., 6–6–40–403 Aobaaramaki-aza, Aoba-ku, Sendai-shi, Miyagi 890–8579, Japan (Received December 28, 2018; accepted in revised form January 25, 2019; published online April 26, 2019)","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2019-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437450","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
To reveal the melting behaviors of core internals mechanistically and to reduce the uncertainties of existing severe accident analysis codes, a numerical simulation code for melt relocation and accumulation behaviors based on computational fluid dynamics named JUPITER has been developed by JAEA. In this paper, we performed a simulation of the accumulation and spreading of a melt to the pedestal region of a typical BWR containment vessel by JUPITER to consider a method for estimating the fuel debris composition. We performed recriticality analysis by the continuous energy neutron transport Monte Carlo code MVP using detailed fuel debris composition data obtained by JUPITER to evaluate recriticality for fuel debris. It was revealed that JUPITER has the potential to obtain a com-plicated fuel debris distribution mechanistically. Also, in effective multiplication factor analyses, we investigated the effect of parameters （ uranium enrichment, water content ratio and partitioning resolution in MVP analysis ） on the effective multiplication factor. It was also revealed that the partitioning resolution is one of the most important factors in JUPITER-MVP coupled analysis, and an appro-priate partitioning according to the inhomogeneity of the fuel debris distribution obtained by JUPITER will be very important.
{"title":"Coupled Analysis of Fuel Debris Distribution and Recriticality by both Multiphase/Multicomponent Flow and Continuous Energy Neutron Transport Monte Carlo Simulations","authors":"S. Yamashita, Kenichi Tada, H. Yoshida, K. Suyama","doi":"10.3327/TAESJ.J17.026","DOIUrl":"https://doi.org/10.3327/TAESJ.J17.026","url":null,"abstract":"To reveal the melting behaviors of core internals mechanistically and to reduce the uncertainties of existing severe accident analysis codes, a numerical simulation code for melt relocation and accumulation behaviors based on computational fluid dynamics named JUPITER has been developed by JAEA. In this paper, we performed a simulation of the accumulation and spreading of a melt to the pedestal region of a typical BWR containment vessel by JUPITER to consider a method for estimating the fuel debris composition. We performed recriticality analysis by the continuous energy neutron transport Monte Carlo code MVP using detailed fuel debris composition data obtained by JUPITER to evaluate recriticality for fuel debris. It was revealed that JUPITER has the potential to obtain a com-plicated fuel debris distribution mechanistically. Also, in effective multiplication factor analyses, we investigated the effect of parameters （ uranium enrichment, water content ratio and partitioning resolution in MVP analysis ） on the effective multiplication factor. It was also revealed that the partitioning resolution is one of the most important factors in JUPITER-MVP coupled analysis, and an appro-priate partitioning according to the inhomogeneity of the fuel debris distribution obtained by JUPITER will be very important.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2018-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"46621314","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Yukichi Takamatsu, H. Ishii, Y. Ohishi, H. Muta, S. Yamanaka, E. Suzuki, K. Nakajima, S. Miwa, M. Osaka, K. Kurosaki
Following the accident at the Fukushima Daiichi Nuclear Power Plant in 2011, radioactive nu-clides caused serious contamination. In particular, cesium （ Cs ） and iodine （ I ） are the most important fission products （ FPs ） because they are easily released due to their high vapor pressure. However, their release behavior from nuclear fuels during the accident has not been clarified. Understanding such behavior can contribute to improving the accuracy of the source term evaluation. Simulated nuclear fuels containing non-radioactive FPs can be used in laboratory experiments to understand such behavior. However, simulated nuclear fuels containing Cs and I are difficult to synthesize because of their high volatility. Here, cerium dioxide （ CeO 2 ） -based simulated fuels containing cesium iodide （ CsI ） are synthesized by spark plasma sintering, allowing us to obtain bulk samples rapidly at low temperatures compared with those of conventional sintering methods. CeO 2 is used to simulate uranium dioxide （ UO 2 ） owing to its similar chemical and physical properties to those of UO 2 . The obtained simulated fuels are characterized by X-ray diffraction and scanning electron microscopy / energy dis-persive X-ray spectrometry. CsI is confirmed to exist as small precipitates almost uniformly distribut-ed throughout the CeO 2 matrix. The optimized conditions to synthesize the simulated fuels are pro-posed.
{"title":"Synthesis and Characterization of CeO2-Based Simulated Fuel Containing CsI","authors":"Yukichi Takamatsu, H. Ishii, Y. Ohishi, H. Muta, S. Yamanaka, E. Suzuki, K. Nakajima, S. Miwa, M. Osaka, K. Kurosaki","doi":"10.3327/TAESJ.J17.025","DOIUrl":"https://doi.org/10.3327/TAESJ.J17.025","url":null,"abstract":"Following the accident at the Fukushima Daiichi Nuclear Power Plant in 2011, radioactive nu-clides caused serious contamination. In particular, cesium （ Cs ） and iodine （ I ） are the most important fission products （ FPs ） because they are easily released due to their high vapor pressure. However, their release behavior from nuclear fuels during the accident has not been clarified. Understanding such behavior can contribute to improving the accuracy of the source term evaluation. Simulated nuclear fuels containing non-radioactive FPs can be used in laboratory experiments to understand such behavior. However, simulated nuclear fuels containing Cs and I are difficult to synthesize because of their high volatility. Here, cerium dioxide （ CeO 2 ） -based simulated fuels containing cesium iodide （ CsI ） are synthesized by spark plasma sintering, allowing us to obtain bulk samples rapidly at low temperatures compared with those of conventional sintering methods. CeO 2 is used to simulate uranium dioxide （ UO 2 ） owing to its similar chemical and physical properties to those of UO 2 . The obtained simulated fuels are characterized by X-ray diffraction and scanning electron microscopy / energy dis-persive X-ray spectrometry. CsI is confirmed to exist as small precipitates almost uniformly distribut-ed throughout the CeO 2 matrix. The optimized conditions to synthesize the simulated fuels are pro-posed.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2018-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.3327/TAESJ.J17.025","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"45117633","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"低温，低酸素および高pH条件下におけるZr-2.5 wt％Nb合金(ふげん圧力管)の腐食速度の算出","authors":"圭一 酒谷, 隆良 中谷, 英之 船橋","doi":"10.3327/TAESJ.J14.032R","DOIUrl":"https://doi.org/10.3327/TAESJ.J14.032R","url":null,"abstract":"","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"14 1","pages":"261-267"},"PeriodicalIF":0.0,"publicationDate":"2015-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"69437164","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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